ML17252A246

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Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B
ML17252A246
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/04/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)


Text

.* . Comrnonv.h Edison

  • Dresde,1 Nuclear Power Station R.R. #i Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #76-775 November 4, 1976 Mr. James G~ Keppler, Regional Director Directorate of R~gulatory Operations -.Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable Occurrence report number 50-249/1976-23.

This report is being submitted to your office in accordance with the Dresden Nuclear Powe~ Station Techriical ~pecifications, Section 6.6.B.

A n n.: .*1Y).. _/) ~. * -I- .

h un~ ~

. B. Stephensori

  • tation Superintendent. .

Dresden Nuclear Power Station BBS :jo Enclosure cc: Director of Inspection & *Enforcement

. Direct'or of Management Information & Program Control File/NRC

~* . LICENSEE EVd\JT REPOR. *. -. . *..

' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)

' 1 6 LICENSEE LICENSE EVENT

  • < NAME LICENSE NUMBER TYPE TYPE

.@El II I L. ID IR I s 13 I 10101-10101010101-10101 1!1111111111 10131 7 8 9 ' 14 15 25 26 ' 30 '31 ' 32' REPORT REPORT CATEGORY TYPE. SOURCE OOCl\ET NUM6ER

  • EVENT* DATE REPORT DATE lof1 IcoN1 I I I llJ LLl 101s101~101~1~191 11 IOIOl?l71(,l .*II II 1014171(, L 7 8 57 58' 59 60 61 68 69 74 75 80 EVENT DESCRIPTION .

(filg].lD!JRtAJ.G- REFUELING- OUTAGE LDC.AL l.t:Ak-:-RATE TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80.

7 lol31Ei' 9ltSO.L..ATION'.

CA*IE:CI<

VfU;V 3-!S-O/-J.5&

£XHtBtT£.D A l...EAr<AC-£ RAT£.... U!J'

' ' 80 I,

7

~ IEXC£$$'0F /HT:; T£CH SP£.C. /_JM/{ OF .J.Cf.~f!/_. SC'l="H. TH OTH~g*. VAL.VE:

8 9' ' ' ' 80 I

10'581 lusED VO f6R<YYI THE. 4'?'-Psf(:; PRESSUfV~ DECAY 7EST BouJVDl1R..Y .. fYlANuALf 7 9 i ' ' ' ' ' " 80 lolsl I VAt..VE'.' 3- 15°0! -:Y,,B J 1-lfJD A $ IGNI FICA NT WATER HC/IJ) PR£s£NTj CONSEQLJOJT1..y,, I 7 8 9. * .. . PRIME * . (5,£ /IT!FICHEV -<;;ft£GT) 80

.

  • SYSTEM CAUSE COMPONENT COMPON!:NT - .

. CODE CODE

  • COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

@0 ISIFLlsJ 1v1AIL1v1£1x1 lt!J 1A1s1*~1s1 L'Ll 7 8 9 10 ' 11 12 17 ' 43 44 47 48

. CAUSE DES.CA!PTION

~ l::TJ1£ VA/..-1/E f:fll L-UR.6 'WA~ CAUSED Bi EXCESS I 116 ])15C-To -SEAi 1-£AKAG-~. J 7 8 9 ' 80 lo'91 l1r1cs J.£AK-fK-G: i,.JA~ A77R.t8UIED, ..To TH£ PREsEl'JCG.* OE DtRTA*No

  • SIYIAL-t~ I 7 8 9 ' ', ' ' ' 80. '

,.~.: (iE1 .I S:CRATc.HC:S OtJ THE Vf/LV~ $£fl'0 APPARENTLY IHE REs()t,..T oF.Jv'ORWl,fiL .W£AR. J

' 7 ;*, 8 9 ,: FACILllY ' METHOD OF ' 'Js:t:E-:/rrjA~/t;F,.P ~}:/.!) . co

' STATUS * %.. POWER OTHER STATUS - OISCOVEAY

  • DISCOVERY DESC.RIPTION EE] , 9*lHJ
  • lO 16 l *6112 *1..__"'""-'.AJ'--A_ ___,I44 .** lBJ ,__,,..-.N-.;,..11'-'--.---~..,.-.-'-._-_ ___,!

. 7.

  • 0** * .10
  • 13 45 **. 46 so FORM OF ACTIVITY CONTENT rn .lZJ 7 8
  • RELEASED 9

OF RELEASE

  • l~J 10 11 AMOUNT OF ACTIVITY
  • I.__*--~N_ll_ _______.

44 I

45 '

LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER *

  • TYPE DESCRIPTION

~ lo Io JO11I : *~ . ~-.....::.JtJ_tt~--,---.,.---------~-------~-~-"-'-'-'-:-'-'------__.___,

7 * *a s 12.. 13 ea.

'. PERS'ONNEL INJURIES NUMBER . OESCRIPTION v.

[EJ*1n10.l.ol L - -.

._ * * -
  • _A_f1_._*- - - - - - - - - - - - - - - - - - - - J 7 8 ~ 11 12 80 OFFSITE CONSEQUENCES

.Elfil I A/A 7 8 9 80

. LOSS ~F;l DAMAGE . TO FACILITY TYPE .DESCRIPTION *

~ .~ A)ff' 7 8 9 10 80 PUBLICITY l:illl8 7 81..;_---L.~L-----------------,-------------'-----.,---~--'-----"------.---::-2~J ADDITIONAL FACTOfiS (1JUJ /v*>0' 7 89 80 EEi89 7 BC NAME: _ _ R;._A_/i_V_])_o_'-_**_?_1:...... 1 _c_.*_w_c._:-_r_D_M_'E----'R"-.---~ PHONE: £xT. d...G 5

EVENT DESCRIPTION (Continued) the as-found leakage of 61.0 SCFH was attributed entirely to leakage through check valve 1501-25B. A second leak test using valves 1501-26B, i501-22B, and 1001-SB as boundaries yielded a leakage rate of 4.2 SCFH: Since .the second test volume included the volume of the previous test, total through-leakage for the penetration was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal leak~rate testing in early 1975. (50-249/1976-23)

CAUSE DESCRIPTION. (Continued)

The valve was disassembled, the seat was lapped, and the packing and _Flexitallic gasket were replaced. Leak-rate testing of the reassembled valve was satisfactory.

In 1975, a test/drain line was installed on this penetration which permitted leak-rate testing of check valve 3-1501-25B for the first time since unit oper-ation began. Since this valve has performed* satisfactorily over a period of .

several years, testing of this vaLve on an approximately annual basis should permit timely identification of a recurring problem.

  • Valve 3-15.0l-25B is a 16-inch tilting disc check valve, manufactured by.Atwood and Morrill Company, Inc.

~ ..

.